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Event Notification Report for January 14, 2003




                    U.S. Nuclear Regulatory Commission

                              Operations Center



                              Event Reports For

                           01/13/2003 - 01/14/2003



                              ** EVENT NUMBERS **



39505  39506  39507  



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|Power Reactor                                    |Event Number:   39505       |

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| FACILITY: HOPE CREEK               REGION:  1  |NOTIFICATION DATE: 01/13/2003|

|    UNIT:  [1] [] []                 STATE:  NJ |NOTIFICATION TIME: 02:48[EST]|

|   RXTYPE: [1] GE-4                             |EVENT DATE:        01/12/2003|

+------------------------------------------------+EVENT TIME:        23:04[EST]|

| NRC NOTIFIED BY:  RITA BRADDICK                |LAST UPDATE DATE:  01/13/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD CONTE        R1      |

|10 CFR SECTION:                                 |                             |

|AIND 50.72(b)(3)(v)(D)   ACCIDENT MITIGATION    |                             |

|                                                |                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     N          Y       100      Power Operation  |100      Power Operation  |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| OPEN  DUCTWORK ACCESS PANEL PREVENTED MAINTAINING CONTROL ROOM POSITIVE      |

| PRESSURE                                                                     |

|                                                                              |

| "On January 12, 2003 at 2304, control room pressure was observed to be       |

| negative. At the time the "A" Control Room Emergency Filtration (CREF)       |

| system was tagged out for scheduled maintenance. The event was initiated     |

| when technicians opened an access panel on the "A" CREF control room air     |

| supply duct within the control room boundary to repair a gasket. This        |

| resulted in both "A" and "B" trains of CREF unable to perform its design     |

| safety function: specifically, maintaining the control room at a 1/8 inch    |

| water gauge positive pressure relative to adjacent areas. Without assurance  |

| of CREF system providing positive pressure in the control room, mitigating   |

| the consequences of an accident could have been prevented. Upon discovering  |

| the cause, technicians were ordered to close the access panel. Control room  |

| pressure promptly returned to a normal, positive value. Total time at        |

| negative pressure was ten minutes. No unexpected response was experienced.   |

| In addition to the "A" CREF train, the "A" Hydrogen/Oxygen analyzer was      |

| inoperable at the time of the event."                                        |

|                                                                              |

| The licensee has notified the NRC resident inspector.                        |

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|Power Reactor                                    |Event Number:   39506       |

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| FACILITY: INDIAN POINT             REGION:  1  |NOTIFICATION DATE: 01/13/2003|

|    UNIT:  [] [3] []                 STATE:  NY |NOTIFICATION TIME: 08:47[EST]|

|   RXTYPE: [2] W-4-LP,[3] W-4-LP                |EVENT DATE:        01/13/2003|

+------------------------------------------------+EVENT TIME:        06:18[EST]|

| NRC NOTIFIED BY:  ANDREW BARTLIK               |LAST UPDATE DATE:  01/13/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |RICHARD BARKLEY      R1      |

|10 CFR SECTION:                                 |JOHN HANNON          NRR     |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|                                                   |                          |

|3     M/R        Y       100      Power Operation  |0        Hot Standby      |

|                                                   |                          |

+------------------------------------------------------------------------------+

                                   EVENT TEXT                                   

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| MANUAL REACTOR TRIP DUE TO LOSS OF CONDENSER CIRCULATING WATER PUMP          |

|                                                                              |

| At 0618 EST the #35 Circulating Water Pump tripped.  The other circulating   |

| water pump supplying the same condenser section was out of service for       |

| maintenance.  The resulting loss of all circulating water to one condenser   |

| section produced a high differential pressure between sections. The reactor  |

| was manually tripped in accordance with plant procedures.  All controlled    |

| rods fully inserted. The Auxiliary Feedwater Pump automatically started as   |

| expected.  During the transient, the #32 Reactor Coolant Pump tripped due to |

| an unknown cause and is being investigated.  Additionally, the # R14 Plant   |

| Vent Gas radiation monitor went into alarm and then immediately returned to  |

| normal, however the redundant monitor did not show any increase in           |

| radiation.  Additionally, the #32 Source Range Detector did not come on      |

| scale on the reactor trip, however the redundant detector functioned         |

| normally.  The electrical system responded normally.  There were no releases |

| associated with this event.  The cause of the circulating water pump trip is |

| under investigation.                                                         |

|                                                                              |

| The licensee has notified the NRC resident inspector.                        |

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+------------------------------------------------------------------------------+

|Power Reactor                                    |Event Number:   39507       |

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| FACILITY: SURRY                    REGION:  2  |NOTIFICATION DATE: 01/14/2003|

|    UNIT:  [1] [] []                 STATE:  VA |NOTIFICATION TIME: 04:18[EST]|

|   RXTYPE: [1] W-3-LP,[2] W-3-LP                |EVENT DATE:        01/14/2003|

+------------------------------------------------+EVENT TIME:        01:37[EST]|

| NRC NOTIFIED BY:  ALISON MACKELLAR             |LAST UPDATE DATE:  01/14/2003|

|  HQ OPS OFFICER:  MIKE RIPLEY                  +-----------------------------+

+------------------------------------------------+PERSON          ORGANIZATION |

|EMERGENCY CLASS:          NON EMERGENCY         |ROBERT HAAG          R2      |

|10 CFR SECTION:                                 |                             |

|ARPS 50.72(b)(2)(iv)(B)  RPS ACTUATION - CRITICA|                             |

|AESF 50.72(b)(3)(iv)(A)  VALID SPECIF SYS ACTUAT|                             |

|                                                |                             |

|                                                |                             |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|UNIT |SCRAM CODE|RX CRIT|INIT PWR|   INIT RX MODE  |CURR PWR|  CURR RX MODE   |

+-----+----------+-------+--------+-----------------+--------+-----------------+

|1     M/R        Y       100      Power Operation  |0        Hot Shutdown     |

|                                                   |                          |

|                                                   |                          |

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                                   EVENT TEXT                                   

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| MANUAL REACTOR TRIP DUE TO HIGH REACTOR COOLANT PUMP SHAFT VIBRATION         |

|                                                                              |

| "At 0137 hours, with Surry Power Station Unit 1 at 100% reactor power, a     |

| manual reactor trip was initiated due to elevated shaft vibrations (alert    |

| and danger) on "C" Reactor Coolant Pump.                                     |

|                                                                              |

| IRPI indication for one control rod indicated 25 steps following the trip.   |

| Borated as necessary to ensure adequate shutdown margin. All other control   |

| rods fully inserted into the core as designed.  The IRPI indication for this |

| rod is trending down at this time. The shutdown margin for Unit 1 was        |

| determined to be satisfactory.  Auxiliary feedwater automatically initiated  |

| as designed on low low steam generator level following the trip.  Primary    |

| RCS temperature decreased to approximately 541 degrees following the reactor |

| trip and was stabilized at 547 degrees.                                      |

|                                                                              |

| "No primary safety or power operated relief valves were actuated during the  |

| event. As a result of the loss of turbine load, the secondary power operated |

| relief valves actuated during the transient. No indication of primary to     |

| secondary leakage exists, therefore no adverse radiological consequences     |

| resulted from this event.                                                    |

|                                                                              |

| "All electrical busses transferred properly following the trip.  #1 EDG was  |

| T/O [tagged out] prior to unit trip.  All other emergency diesel generators  |

| are operable.  There were no radiation releases due to this event, nor were  |

| there any personnel injuries or contamination events.  The cause of the      |

| event is being investigated.                                                 |

|                                                                              |

| "Unit 1 is currently at Hot Shutdown with RCS temperature being maintained   |

| at approximately 547 degrees.  Unit 2 was not affected by this event and     |

| remains stable at 100% power operations.  This event Is being reported In    |

| accordance with 10CFR50.72(b)(2)(iv) and I0CFR50.72(b)(3)(iv)."              |

|                                                                              |

| The licensee notified the NRC resident inspector.                            |

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